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| | The Light company PO llox 1700 llouston, he 77001 (715) :' m M it ilouston 1.ightingk Power December 21, 1990 ST llL AE 3659 File No.: 09.06, C20.01 10CTR$0.90 10CFR50.92 10CTR$0.54(f) l i |
| | U. S. Nuclear Regulatory Conunission l Attention: Document Control Desk l Washington, DC 20555 ) |
| | South Texas Project Elcetric Generating Station Units 1 6 2 Docket Nos. STN $0 498, STN $0 499 Response to Generic Latter 90 06 |
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| | ==Reference:== |
| | (1) Letter ST llL AE 3642, dated December 22, 1990 from S. L. |
| | Rosen (STPECS) to the USNRC Document Control Desk Attached is the response to Generic Letter 90 06, Resolution of Generic Issue 70, " Power Operated Relief Valve and Block Valve Reliability," |
| | and Generic Issue 94, " Additional Low Temperature Overpressure Protection for Light Water Reactors." |
| | Pursuant to 10Cril50.54(f) the staf f requested that actions identified in Generic Letter GL 90 06 be taken by liccusees in order to increase plant safety and reliability. Implementation of the 10CPR50.54(f) request. requires lilAP to modify Technical Specifications 3/4.4.4 and 3/4.4.9.3. Reference 1 proposes an Amendment to Operating Licenses NPF 76 and NPF 80 to change the Technical Specifications for the South Texas Project Electric Generating Station (STPEGS) Units 1 and 2. The proposed changes to the STPECS Technical Specifications incorporate the recommendations provided in Enclosure A and Enclosure B of Generic Letter 90 06. Implementation of these actions resolves Generic Issues 70 and 94 for STPEGS. |
| | If you should have any questions concerning this matter, please contact Mr. A. W. liarrison at (512) 972 7298 or myself at ($12) 972 7138 S. L.'Rosen Vice President, Nuclear Engineering SDP/sgs Attachments: 1. Response to Generic Letter 90 06 k(j |
| | : 2. Proposed Technical Specification Changes (h \ |
| | A1/039.N19 A Subsidiary of llouston Indmtries In00tpotated k 9012280174 901221 PDR ADOCK 05000498 p PDR |
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| | ! ST.HL AE.3659 Ilouston Lighting & Power Company File No.: 0 9. 06, C 2 0. 01 . |
| | , South Teams Project Electric Generating Statiot. Page 2-cc: |
| | Regional Administrator, Region IV Rufus S. Scott Hucicar Regulatory Commission Associate General Counsel 611 Ryan Plaza Drive, Suite 1000 llouston Lighting & Power Company Arlington, TX 76011 P. O. Box 61867 llouston, TX 77208 Ceorge Dick, Project Manager U.S. Nuclear Regulatory Commission INPO Washington, DC 20!55 Records Center . |
| | 1100 circle 75 Parkway J. I. Tapia Atlanta, CA 30339 3064 Senior Resident inspector " |
| | c/o U. S. Nuclear Regulatory Dr. Joseph M. llendrie Commission $0 Be11 port Lane P.- O. Box 910 Be11 port, NY 11713 Bay City, TX 77414 D. R. Lacker J. R. Newman, Esquire Bureau of Radiation Control Newman & lloitzinger, P.C. Texas Department of llealth 1615 L Street,. N.W. 1100 West 49th Street Washington, DC 20036 Austin, TX 78756 3189 R. P. Verret/D. E. Ward Central Power & Light Company P. O. Box 2121 r Corpus Christi, TX 78403 l |
| | J. C. Lanier/M. B. Lee City of Austin Elcetric Utility Department P.O. Box 1088 Austin, TX 78767 R. J. Costello/M. T. liardt City Public Service Board P. O. Box 1771 San Antonio, TX 78296 i |
| | Revised 10/08/90 L4/NRC/ |
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| | i UNITED STATES OF AMERICA NUCLEAR REGUIATORY COMMISSION I In the matter ) ' |
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| | ilouston Lighting 6 Power ) Dock Nos. 50 498 Company,'et al.,- ) 50 499 ; |
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| | South Texas Project ) |
| | Units 1 and 2 ) |
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| | AFFIDAVIT S. L. Rosen being duly sworn, hereby deposes and says that he is |
| | , .Vice President, Nuclear Engineering of Houston Lighting 6 Power Cotopany; that |
| | ;. he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached response to PRC Ceneric Letter 90 06; is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge and belief. |
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| | S. L. Rosen Vice-President, Nuclear Engineering GTATE OF TEXAS ) |
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| | ) |
| | Subscribedapdsworntobeforeme,aNotaryPublicinandfor- |
| | -The State of Texas thiad day of 2/cemkW/ , 1990. |
| | O . |
| | ,digey,,,, "' : Notary Puutio in and for tue |
| | " . gs,,,,/ |
| | < -Mewnentanian.,f State f Texas , |
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| | ="W I |
| | 1 A1/039.N19 i |
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| | ; - Attachment 1 i |
| | ST HL AE 3659 Page 1 of 4 RP.SPONSE TO GENERIC Lb"PTER 90-06 Generic Letter 90 06 provided resolution of Generic Issue 70, |
| | * POWER OPERATED RELIEP VALVE AND BLOCK VALVE RELIABILITY," and Generic Issue 94, " ADDITIONAL LOW TEMPERATURE OVERPRESSURE PROTECTION POR LIGHT WATER REACTOR $". This Generic Letter requested that Licensees complete the actions identified in Section 3 of Enclosures A and B to enhance safety. Implementation of the requested actions resolves Generic Issues 70 and 94 for STPEGS. ! |
| | , 1 Section 3 of Enclosure A to Generic Letter 90 06 provides actions which should be taken to improve tLe reliability of Power Operated Relief Valves (PORVs) and block valves. Tho specific actions and the HL&P response are provided below: |
| | Action 1. |
| | Include PORVs and blotk valves within the scope of an operational quality ) |
| | assurance program that is in compliance with 10 CIR 50. Appendix B. This program should include the following elements: |
| | : a. The addition of PORV.1 and block valves to the plant operational Quality Assurance Lint. |
| | |
| | ===Response=== |
| | The PORVs and block valves.are specified as safety class 1 valves and are included in the STPEGS Project Q List, |
| | : b. ' Implementation of a maintenance / refurbishment program for PORVs and block valves that is based on the manufacturer's recommendations or guidelines and is implemented by trained plant maintenance personnel. |
| | Response: , |
| | These valvea are included in the STPEGi meiutenance program which incorporates the manufactuier's guidelines and reconnendations. Required maintenance is specified in thu Grecial Equipment Qualification Maintenance Book (SEQHB) and is performed by trained maintenance personnel. |
| | : c. When repinecoent parts and spares, as well as complete components, are required for existing non safoty grado PORVs and block valves (and associated control systems), it is the intent of this generic letter that these items may be procured in accordance with the original construction codes and standards. |
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| | ===Response=== |
| | The STPEGS PORVs and block valves are safety grade valves. Repincement parts, spares and components are procured in accordance with the original construction codes and standards. |
| | A1/039,N10 |
| | . . _ __ , , __ - . _ - ,_- _ . . ~ _ . |
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| | Attachment 1 l ST ill AE 36$9 j |
| | ] Page 2 of 4 l 1 i |
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| | ! Action 2. ; |
| | Include PORVs, valves in PORV control air systems, and block valves i within the scope of a program covered by subrection IWV, |
| | * Inservice Testing of Valves in Nuclear Power Plants," of Section XI of the ASME 4 2 |
| | Boiler and Pressure Vessel code. Stroke testing of PORVs should only bc , |
| | performed during Mode 3 (HOT STANDBY) or Mode 4 (110T SHUTDOWN) and in all j cases prior to establishing conditions where the PORVs are used for l low temperature overpressure protection. Stroke testing of the PORVs l should not be performed during power operation. Additionally, the PORV l block valves should be included in the licensees' expanded MOV test 4 |
| | program discussed in NRC Generic Letter 89 10, " Safety Related Motor Operated Valve Testing and Surveillance," dated June 28, 1989. |
| | |
| | ===Response=== |
| | The STPECS solenoid operated PORVs and block valves are included in the , |
| | inservice Inspection (ISI) program which is covered by Subsection IWV of j Section XI of the ASME code. Stroke testing of the PORVs will not be ! |
| | [ performed during power operations. The conditions under which PORV j stroke testing is performed are provided in Technleni Specification ' |
| | Requirements 4.4.4.1.b 3.4.9.3.b, and 3.4.9.3.c (see Reference 1). The PORV block valves are included-in the STPECS expanded MOV test program. |
| | Action 3. ' |
| | For operating PWR plants, modify the limiting conditionts for operation of PORVs and block valves in the technical specifications for Modes 1. 2, and 3 to incorporate the position adopted by the str.ff in recent Ilcensing actions. Attachments A 1 through A 3 are provided for guidance. The staff recognizes that some recently licensed PWR plants already have technical specifications in accordance with the staff po-sition. Such plants are already in compliance with this position and need merely state that in their response. These recent technical speci*ications require that plants that run with the block valves closed (e.g., due to leaking PORVs) maintain electrical power to the block valves so they can be readily opened from the control room upon demand. |
| | Additionally, plant operation in Modes 1, 2, and 3 with PORVs and block valves inoperable for reasons other than seat leakage is not permitted for periods of more than 72 hours. |
| | |
| | ===Response=== |
| | The guidance provided in Attachment A-1 through A 3 of the Generic Letter is incorporated in-the proposed revision to the STPECS Technical Specifications. The proposed Technical Specification changes which incorporate this guidance are given in Reference.1. |
| | Section 3 of Enclosure B to Generic Letter 90 06 provides additional administrative restrictions on the Low Temperature Overpressure Protection (LTOP) system which improve the protection system availability. As stated in the Staff position, revision of the current Technical Specification for i Overprotection Protection to reduce the A0T for a single channel in modes 5 1. |
| | j A1/039.N19 |
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| | Attachment 1 ST.}lL. AE. 3659 Page 3 of 4 and 6 from 7 days to 24 hours provides additional assurance that plant operation is consistent with the design basis transient analysis. In addition, the Staff has requested that administrative controls and procedures which are identified in Section 1 of Enclosure B to the Generic Letter and which are incorporated into the plant design basis should be implemented now 1R the teatrictions were not implemented as part of USI A 26. These administrative controls and procedures shich were identified as part of Multi-Plant Action Item B 04 include the following items: |
| | : 1. Minimize the time the reactor coolant system (RCS) is maintained in a water solid condition. |
| | : 2. Restrict the number of high pressure pumps operable to no more than one when the RCS is in the LTOP condition. |
| | : 3. Ensure that-the steam generator to RCS temperature difference is less than 50 Deg F when a reactor coolant pump (RCP) is bein6 started in a water solid RCS. |
| | 4 Set the PORV setpoint (if the particular plant relies on this 1 component for LTOP) to a plant + specific analysis supported value, and have surveillance that checks the PORV actuation electronics and setpoint. |
| | |
| | ===Response=== |
| | The revised Technical Specification for the STPECS Cold Overpressure Mitigation System (COMS) is provided in Reference 1. This revised Technical Specification 3.4.9.3 reduces the A0T from 7 days to 24 hours as requested. The administrative controls and procedures discussed in Section 1 of Enclosure B of the Generic Letter are incorporated into the STPECS procedures as follows: |
| | : 1. The time that the RCS is water solid is minimized by the STPECS plant operating procedures and administrative controls. The RCS is placed in a water solid condition only during cooldown and filling and venting operatiens. The need to minimize the time that the plant is maintained in a water solid condition will be included in operator training. |
| | : 2. The current STPECS Technical Specifications allow only one liigh llead Safety Injection (511151) pump to be OPERABLE and a second lillS1 pump OPERABhE with its dreaker racked out in MODE 4 (ref. Technical specification LCO 3.u.3 1). All 111151 pumps are to be inoperabic in HODES 5 & 6 with the reactor vessel head on (ref. Technical Specification LCO 3.5.3.2). The current STPEGS Technical Specification requirements comply with the intent of item 2 of Multi-Plant Action item. |
| | A1/039,N19 Y |
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| | At t achinent 1 i |
| | ST l!L AE 3659 Page 4 of 4 |
| | : 3. The restriction on starting a RCP during water solid operations with the steam generator secondary side water temperature greater than 50*F above the RCS temperature is provided in the current STPECS Technical Specifications (ref. Technical Specification LCO 3.4.1.3). |
| | : 4. The PORV setpoints are based on plant specific analysis which ensures compliance with the 10 CFR 50 Appendix G liroits. The surveillance requirements for the PORV actuation electronics and setpoints are provided in current Technical Specification Requirements 4.4.4.1.a. |
| | 4.4.9.3.1.a and 4.4.9.3.1.b. |
| | A1/039,1(19 |
| | _ _ _ _ - . . _ _ _ _ _ _ _ _ _ - _ _ _ . _ _ _ _ -}} |
Forwards Response to Generic Ltr 90-06, Resolution of Generic Issue 70, 'Porv & Block Valve Reliability' & Generic Issue 94, 'Addl Low Temp Overpressure Protection for Lwrs.' License Amend Submitted on 901222 Re Generic LtrML20065T527 |
Person / Time |
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Site: |
South Texas ![STP Nuclear Operating Company icon.png](/w/images/9/9c/STP_Nuclear_Operating_Company_icon.png) |
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Issue date: |
12/21/1990 |
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From: |
Rosen S HOUSTON LIGHTING & POWER CO. |
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To: |
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
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References |
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REF-GTECI-070, REF-GTECI-094, REF-GTECI-NI, TASK-070, TASK-094, TASK-70, TASK-94, TASK-OR GL-90-06, GL-90-6, ST-HL-AE-3659, NUDOCS 9012280174 |
Download: ML20065T527 (7) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARNOC-AE-000675, Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested1999-10-21021 October 1999 Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested NOC-AE-000680, Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan1999-10-20020 October 1999 Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan NOC-AE-000683, Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii)1999-10-19019 October 1999 Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii) ML20217K9341999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-4 for Relief from ASME Code,Section XI, Nondestructive Exam Requirements Applicable to Stp,Units 1 & 2,reactor Vessel Closure Head Nuts ML20217K9091999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-3 from ASME Code,Section Xi,Nondestructive Exam Requirements Applicable to South Texas Project,Units 1 & 2, Pressurizer Support Attachment Welds 05000498/LER-1999-008, Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER1999-10-12012 October 1999 Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER NOC-AE-000674, Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule1999-10-12012 October 1999 Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule NOC-AE-000625, Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future1999-10-0707 October 1999 Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future NOC-AE-000610, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i) NOC-AE-000653, Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i) ML20217C3221999-10-0707 October 1999 Forwards Insp Repts 50-498/99-16 & 50-499/99-16 on 990808-0918.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls 05000499/LER-1999-006, Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment1999-09-30030 September 1999 Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment ML20212L1651999-09-30030 September 1999 Responds to STP Nuclear Operating Co 981012 & s Which Provided Update to TS Bases Pages B 3/4 8-14 Through B 3/4 8-17.NRC Staff Found Change Consistent with TS 3/4.8.2 DC Sources. Staff Found & Deleted Typographical Error NOC-AE-000664, Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr1999-09-30030 September 1999 Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr ML20212J7141999-09-29029 September 1999 Forwards Insp Repts 50-498/99-15 & 50-499/99-15 on 990920-24 at South Texas Project Electric Generating Station.No Violations Noted.Insp Covered Requalification Training Program & Observation of Requalification Activities NOC-AE-000646, Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr1999-09-28028 September 1999 Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr ML20212J0651999-09-27027 September 1999 Discusses Licensee 980330 Response to GL 97-06, Degradation of SG Internals. Concludes That Response to GL Provides Reasonable Assurance That Condition of SG Internals in Compliance with Current Licensing Bases for Facility ML20212F1791999-09-24024 September 1999 Discusses 990923 Meeting Conducted in Region IV Ofc Re Status of Activities to Support Confirmatory Order, ,modifying OL & to Introduce New Director,Safety Quality Concerns Program.List of Attendees Encl ML20212E9091999-09-23023 September 1999 Discusses GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Supplement 1 & STP Nuclear Operating Co Response for STP Dtd 990629.Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient ML20212F2111999-09-22022 September 1999 Forwards Review of SG 90-day Rept, South Texas Unit-2 Cycle 7 Voltage-Based Repair Criteria Rept, Submitted by Util on 990119 NOC-AE-000633, Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 19971999-09-21021 September 1999 Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 1997 NOC-AE-000634, Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl1999-09-21021 September 1999 Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl NOC-AE-000649, Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P1999-09-21021 September 1999 Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P 05000499/LER-1999-005, Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-09-20020 September 1999 Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER ML20212D9171999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of South Texas Project & Identified No Areas in Which Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through Mar 2000 & Historical Listing of Plant Issues,Encl ML20216F5471999-09-15015 September 1999 Discusses 990914 Meeting Conducted at Region Iv.Meeting Was Requested by Staff to Introduce New Management Organization to Region IV & to Discuss General Plant Performance & Mgt Challenges IR 05000498/19990121999-09-14014 September 1999 Forwards Insp Repts 50-498/99-12 & 50-499/99-12 on 990816-19.Three Violations Occurred & Being Treated as Ncvs. Areas Examined During Insp Included Portions of Access Authorization & Physical Security Programs 05000498/LER-1999-007, Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER1999-09-13013 September 1999 Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER ML20211P8201999-09-0909 September 1999 Forwards SE Authorizing 990224 Submittal of First 10-year Interval ISI Program Plan - Relief Request RR-ENG-24,from ASME Section XI Code,Table IWC-2500-1 NOC-AE-000638, Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-0909 September 1999 Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6) ML20211P7671999-09-0909 September 1999 Forwards SER Authorizing Licensee 990517 Alternative Proposed in Relief Request RR-ENG-2-8 to Code Case N-491-2 for Second 10-year Insp Interval of South Texas Project, Units 1 & 2,pursuant to 10CFR50.55a(a)(3)(i) ML20211P7871999-09-0909 September 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Program Plan Request for Relief RR-ENG-31 IR 05000498/19990141999-09-0303 September 1999 Forwards Insp Repts 50-498/99-14 & 50-499/99-14 on 990627-0807.Apparent Violations Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy NOC-AE-000562, Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i)1999-08-31031 August 1999 Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i) ML20212A4351999-08-27027 August 1999 Discusses Investigation Rept OI-4-1999-009 Re Activites at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination Complaint. Allegation Not Substantiated.No Further Action Planned NOC-AE-000617, Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d)1999-08-26026 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d) ML20211J2511999-08-26026 August 1999 Discusses Proposed TS Change on Replacement SG Water Level Trip Setpoint for Plant,Units 1 & 2 NOC-AE-000585, Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-4811999-08-25025 August 1999 Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-481 ML20211F4421999-08-24024 August 1999 Forwards SE Authorizing Licensee 990513 Request for Relief RR-ENG-2-13,seeking Relief from ASME B&PV Code Section Xi,Exam Vessel shell-to-flange Welds for Second ISI Intervals ML20211F5031999-08-23023 August 1999 Forwards SE Authorizing Licensee 990315 Request for Relief RR-ENG-30,seeking Relief from ASME B&PV Code,Section Xi,Nde Requirements Applicable to Stp,Unit 2 SG Welds ML20212A4391999-08-17017 August 1999 Discusses Investigation Rept OI-4-1999-023 Re Activities at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination for Initiating Condition Report to Document Unauthorized Work Practices ML20210U1271999-08-16016 August 1999 Forwards Insp Repts 50-498/99-08 & 50-499/99-08 on 990517-21 & 0607-10.No Violations Noted.Corrective Action Program Was Reviewed ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams NOC-AE-000603, Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6)1999-07-29029 July 1999 Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6) NOC-AE-000470, Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl1999-07-28028 July 1999 Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl NOC-AE-000599, Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr1999-07-28028 July 1999 Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr NOC-AE-000589, Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/20001999-07-26026 July 1999 Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/2000 ML20210F3851999-07-26026 July 1999 Forwards Exam Repts 50-498/99-301 & 50-499/99-301 on 990706- 15.Exam Included Evaluation of 9 Applicants for SO Licenses & 8 Applicants for RO Licenses 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARNOC-AE-000675, Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested1999-10-21021 October 1999 Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested NOC-AE-000680, Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan1999-10-20020 October 1999 Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan NOC-AE-000683, Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii)1999-10-19019 October 1999 Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii) NOC-AE-000674, Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule1999-10-12012 October 1999 Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule 05000498/LER-1999-008, Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER1999-10-12012 October 1999 Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER NOC-AE-000625, Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future1999-10-0707 October 1999 Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future NOC-AE-000610, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i) NOC-AE-000653, Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i) 05000499/LER-1999-006, Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment1999-09-30030 September 1999 Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment NOC-AE-000664, Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr1999-09-30030 September 1999 Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr NOC-AE-000646, Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr1999-09-28028 September 1999 Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr NOC-AE-000633, Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 19971999-09-21021 September 1999 Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 1997 NOC-AE-000634, Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl1999-09-21021 September 1999 Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl NOC-AE-000649, Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P1999-09-21021 September 1999 Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P 05000499/LER-1999-005, Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-09-20020 September 1999 Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER 05000498/LER-1999-007, Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER1999-09-13013 September 1999 Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER NOC-AE-000638, Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-0909 September 1999 Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6) NOC-AE-000562, Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i)1999-08-31031 August 1999 Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i) NOC-AE-000617, Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d)1999-08-26026 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d) NOC-AE-000585, Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-4811999-08-25025 August 1999 Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-481 NOC-AE-000603, Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6)1999-07-29029 July 1999 Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6) NOC-AE-000599, Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr1999-07-28028 July 1999 Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr NOC-AE-000470, Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl1999-07-28028 July 1999 Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl 05000498/LER-1999-006, Forwards LER 99-006-00 Re Automatic Reactor Trip Due to over-temp delta-temp Actuation.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-07-26026 July 1999 Forwards LER 99-006-00 Re Automatic Reactor Trip Due to over-temp delta-temp Actuation.Licensee Commitments Are Listed in Corrective Actions Section of LER NOC-AE-000589, Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/20001999-07-26026 July 1999 Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/2000 NOC-AE-000582, Forwards 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1. Summary Rept Satisfies Reporting Requirements of IWA-6000 of Section XI for Welds & Component Supports1999-07-26026 July 1999 Forwards 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1. Summary Rept Satisfies Reporting Requirements of IWA-6000 of Section XI for Welds & Component Supports NOC-AE-000597, Forwards voltage-based Criteria 90-day Rept for SG Tube Exam Performed Under NRC GL 95-05 During Refueling Outage 1RE08. Rept Contains Info Required by Section 6.b of Attachment 2 to GL 95-051999-07-23023 July 1999 Forwards voltage-based Criteria 90-day Rept for SG Tube Exam Performed Under NRC GL 95-05 During Refueling Outage 1RE08. Rept Contains Info Required by Section 6.b of Attachment 2 to GL 95-05 NOC-AE-000598, Forwards Four Copies of 1RE08 Refueling Outage ISI Summary Rept for Steam Generator Tubing1999-07-23023 July 1999 Forwards Four Copies of 1RE08 Refueling Outage ISI Summary Rept for Steam Generator Tubing NOC-AE-00586, Forwards Results of Control Rod Testing,In Response to NRC Bulletin 96-01, Control Rod Insertion Problems, Dtd 960308.Core Map Provided to Assist in Understanding Test Data1999-07-21021 July 1999 Forwards Results of Control Rod Testing,In Response to NRC Bulletin 96-01, Control Rod Insertion Problems, Dtd 960308.Core Map Provided to Assist in Understanding Test Data NOC-AE-000595, Forwards Chapters 1.0 & 16.0 to Operations QA Plan for South Texas Project.Rev Is Strictly Administrative & All Content Was Previously Submitted to NRC on 990503 & 9906151999-07-21021 July 1999 Forwards Chapters 1.0 & 16.0 to Operations QA Plan for South Texas Project.Rev Is Strictly Administrative & All Content Was Previously Submitted to NRC on 990503 & 990615 NOC-AE-000518, Requests Exemption from Various Special Treatment Requirements of 10CFR50,as Described in Encls to Ltr.Stp Believes That Pilot Application Will Assist NRC in Development & Implementation of risk-informed 10CFR501999-07-13013 July 1999 Requests Exemption from Various Special Treatment Requirements of 10CFR50,as Described in Encls to Ltr.Stp Believes That Pilot Application Will Assist NRC in Development & Implementation of risk-informed 10CFR50 NOC-AE-000536, Submits Request for Exemption from Requirements of 10CFR50.34(b)(11),10CFR50,App A,Gdc 2 & 10CFR100,App a, Section VI(a)(3) Re Maint of Seismic Instrumentation.Revised Page to Procedure OERP01-ZV-IN01 Included1999-07-13013 July 1999 Submits Request for Exemption from Requirements of 10CFR50.34(b)(11),10CFR50,App A,Gdc 2 & 10CFR100,App a, Section VI(a)(3) Re Maint of Seismic Instrumentation.Revised Page to Procedure OERP01-ZV-IN01 Included NOC-AE-000580, Forwards Response to NRC 990415 RAI Re Implementation of Commitments Related to GL 89-10, Safety-Related MOV Testing & Surveillance & GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs1999-07-13013 July 1999 Forwards Response to NRC 990415 RAI Re Implementation of Commitments Related to GL 89-10, Safety-Related MOV Testing & Surveillance & GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs NOC-AE-000574, Forwards ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests Performed Between 971004 & Completion of Eighth RO on 9904281999-07-0606 July 1999 Forwards ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests Performed Between 971004 & Completion of Eighth RO on 990428 NOC-AE-000557, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of App III,III-3410 for Second ISI Interval.Proposed Alternatives for Ultrasonic Exam of Piping Sys Welds,Attached1999-07-0606 July 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of App III,III-3410 for Second ISI Interval.Proposed Alternatives for Ultrasonic Exam of Piping Sys Welds,Attached NOC-AE-000498, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements Applicable to SG Main Steam Nozzle inside- Radius Sections.Attachment Includes Discussion of Basis & Justification for Request & Implementation Schedule1999-07-0606 July 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements Applicable to SG Main Steam Nozzle inside- Radius Sections.Attachment Includes Discussion of Basis & Justification for Request & Implementation Schedule NOC-AE-000573, Requests Relief from Requirements of ASME Section XI Code Case N-498,exempting Isolated Class 1 Reactor Vessel Head Vent Atmospheric Vent Piping & Valve from Being Tested at Full RCS Pressure1999-07-0606 July 1999 Requests Relief from Requirements of ASME Section XI Code Case N-498,exempting Isolated Class 1 Reactor Vessel Head Vent Atmospheric Vent Piping & Valve from Being Tested at Full RCS Pressure NOC-AE-000541, Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Npps. Readiness Disclosure for STP, Encl1999-06-29029 June 1999 Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Npps. Readiness Disclosure for STP, Encl NOC-AE-000571, Forwards Final Operating Exam Matls for STP Exam Scheduled for 990705.Revised Operating Exam Outline & post-validation Change Summary Has Been Included.Without Encls1999-06-24024 June 1999 Forwards Final Operating Exam Matls for STP Exam Scheduled for 990705.Revised Operating Exam Outline & post-validation Change Summary Has Been Included.Without Encls NOC-AE-000512, Responds to NRC 981201 Telcon Re Jco 93-0004,per Revised MSLB Analysis1999-06-23023 June 1999 Responds to NRC 981201 Telcon Re Jco 93-0004,per Revised MSLB Analysis NOC-AE-000560, Forwards LER 99-S02-00,re Failure to Maintain Positive Control of Vital Area Security Key.Licensee Commitments Are Found in Corrective Action Section of LER1999-06-23023 June 1999 Forwards LER 99-S02-00,re Failure to Maintain Positive Control of Vital Area Security Key.Licensee Commitments Are Found in Corrective Action Section of LER 05000498/LER-1999-005, Forwards LER 99-005-00,re Failure to Meet Requirements of TS Surveillance 3.7.1.2 Action B for Auxiliary FW Sys.Only Commitments Contained in Ltr Are Located in Corrective Action Section of LER1999-06-17017 June 1999 Forwards LER 99-005-00,re Failure to Meet Requirements of TS Surveillance 3.7.1.2 Action B for Auxiliary FW Sys.Only Commitments Contained in Ltr Are Located in Corrective Action Section of LER NOC-AE-000565, Forwards Amended Pages for Insertion Into South Texas Project Nuclear Operating Co Previously Submitted Response to NRC Rai.New Pages Include Expanded Answer to Question 4.b1999-06-16016 June 1999 Forwards Amended Pages for Insertion Into South Texas Project Nuclear Operating Co Previously Submitted Response to NRC Rai.New Pages Include Expanded Answer to Question 4.b NOC-AE-000548, Forwards Response to RAI Re Proposed Amends on Replacement SG Water Level Trip Setpoint Differences for Stp,Units 1 & 2.Nothing Contained in Response Should Be Considered Commitment Unless So Specified in Separate Correspondence1999-06-16016 June 1999 Forwards Response to RAI Re Proposed Amends on Replacement SG Water Level Trip Setpoint Differences for Stp,Units 1 & 2.Nothing Contained in Response Should Be Considered Commitment Unless So Specified in Separate Correspondence NOC-AE-000561, Forwards Change QA-042 to Operations QAP, Rev 13, Reflecting Current Organizational Alignment for STP & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months1999-06-15015 June 1999 Forwards Change QA-042 to Operations QAP, Rev 13, Reflecting Current Organizational Alignment for STP & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months NOC-AE-0559, Forwards STP Commitment Change Summary Rept for Period 981209-990610.Rept Lists Each Commitment for Which Change Was Made During Reporting Period & Provides Basis for Each Change1999-06-15015 June 1999 Forwards STP Commitment Change Summary Rept for Period 981209-990610.Rept Lists Each Commitment for Which Change Was Made During Reporting Period & Provides Basis for Each Change NOC-AE-000499, Forwards Relief Request RR-ENG-2-3,proposing to Perform Alternative Ultrasonic Examination from Outside Surface of Skirt Attachment Weld as Described in Encl,In Lieu of Surface Examination from Inside Pressurizer Skirt1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-3,proposing to Perform Alternative Ultrasonic Examination from Outside Surface of Skirt Attachment Weld as Described in Encl,In Lieu of Surface Examination from Inside Pressurizer Skirt NOC-AE-000502, Forwards Relief Request RR-ENG-2-6,proposing That Boroscopic VT-1 Visual Examination Be Allowed as Alternative to Section XI Surface Examination of Pump Casing Welds,Or Portions of Welds within Pits1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-6,proposing That Boroscopic VT-1 Visual Examination Be Allowed as Alternative to Section XI Surface Examination of Pump Casing Welds,Or Portions of Welds within Pits NOC-AE-000500, Forwards Relief Request RR-ENG-2-4,proposing to Perform Alternative Ultrasonic Examination from Outside & End Surfaces of Reactor Vessel Closure Head Nuts,As Described in Encl in Lieu of Surface Examination of Threaded Region1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-4,proposing to Perform Alternative Ultrasonic Examination from Outside & End Surfaces of Reactor Vessel Closure Head Nuts,As Described in Encl in Lieu of Surface Examination of Threaded Region NOC-AE-000545, Forwards Response to NRC 990416 RAI Re Util Proposed Amend on Operator Action for Small Break Loca, .Draft EOP Re Small Break Loca,Encl to Aid Discussion of Proposed Amend1999-05-31031 May 1999 Forwards Response to NRC 990416 RAI Re Util Proposed Amend on Operator Action for Small Break Loca, .Draft EOP Re Small Break Loca,Encl to Aid Discussion of Proposed Amend 1999-09-09
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0 .
The Light company PO llox 1700 llouston, he 77001 (715) :' m M it ilouston 1.ightingk Power December 21, 1990 ST llL AE 3659 File No.: 09.06, C20.01 10CTR$0.90 10CFR50.92 10CTR$0.54(f) l i
U. S. Nuclear Regulatory Conunission l Attention: Document Control Desk l Washington, DC 20555 )
South Texas Project Elcetric Generating Station Units 1 6 2 Docket Nos. STN $0 498, STN $0 499 Response to Generic Latter 90 06
Reference:
(1) Letter ST llL AE 3642, dated December 22, 1990 from S. L.
Rosen (STPECS) to the USNRC Document Control Desk Attached is the response to Generic Letter 90 06, Resolution of Generic Issue 70, " Power Operated Relief Valve and Block Valve Reliability,"
and Generic Issue 94, " Additional Low Temperature Overpressure Protection for Light Water Reactors."
Pursuant to 10Cril50.54(f) the staf f requested that actions identified in Generic Letter GL 90 06 be taken by liccusees in order to increase plant safety and reliability. Implementation of the 10CPR50.54(f) request. requires lilAP to modify Technical Specifications 3/4.4.4 and 3/4.4.9.3. Reference 1 proposes an Amendment to Operating Licenses NPF 76 and NPF 80 to change the Technical Specifications for the South Texas Project Electric Generating Station (STPEGS) Units 1 and 2. The proposed changes to the STPECS Technical Specifications incorporate the recommendations provided in Enclosure A and Enclosure B of Generic Letter 90 06. Implementation of these actions resolves Generic Issues 70 and 94 for STPEGS.
If you should have any questions concerning this matter, please contact Mr. A. W. liarrison at (512) 972 7298 or myself at ($12) 972 7138 S. L.'Rosen Vice President, Nuclear Engineering SDP/sgs Attachments: 1. Response to Generic Letter 90 06 k(j
- 2. Proposed Technical Specification Changes (h \
A1/039.N19 A Subsidiary of llouston Indmtries In00tpotated k 9012280174 901221 PDR ADOCK 05000498 p PDR
I
! ST.HL AE.3659 Ilouston Lighting & Power Company File No.: 0 9. 06, C 2 0. 01 .
, South Teams Project Electric Generating Statiot. Page 2-cc:
Regional Administrator, Region IV Rufus S. Scott Hucicar Regulatory Commission Associate General Counsel 611 Ryan Plaza Drive, Suite 1000 llouston Lighting & Power Company Arlington, TX 76011 P. O. Box 61867 llouston, TX 77208 Ceorge Dick, Project Manager U.S. Nuclear Regulatory Commission INPO Washington, DC 20!55 Records Center .
1100 circle 75 Parkway J. I. Tapia Atlanta, CA 30339 3064 Senior Resident inspector "
c/o U. S. Nuclear Regulatory Dr. Joseph M. llendrie Commission $0 Be11 port Lane P.- O. Box 910 Be11 port, NY 11713 Bay City, TX 77414 D. R. Lacker J. R. Newman, Esquire Bureau of Radiation Control Newman & lloitzinger, P.C. Texas Department of llealth 1615 L Street,. N.W. 1100 West 49th Street Washington, DC 20036 Austin, TX 78756 3189 R. P. Verret/D. E. Ward Central Power & Light Company P. O. Box 2121 r Corpus Christi, TX 78403 l
J. C. Lanier/M. B. Lee City of Austin Elcetric Utility Department P.O. Box 1088 Austin, TX 78767 R. J. Costello/M. T. liardt City Public Service Board P. O. Box 1771 San Antonio, TX 78296 i
Revised 10/08/90 L4/NRC/
t i
i UNITED STATES OF AMERICA NUCLEAR REGUIATORY COMMISSION I In the matter ) '
)
ilouston Lighting 6 Power ) Dock Nos. 50 498 Company,'et al.,- ) 50 499 ;
)
South Texas Project )
Units 1 and 2 )
l; l
AFFIDAVIT S. L. Rosen being duly sworn, hereby deposes and says that he is
, .Vice President, Nuclear Engineering of Houston Lighting 6 Power Cotopany; that
- . he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached response to PRC Ceneric Letter 90 06; is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge and belief.
1 r
.c -
S. L. Rosen Vice-President, Nuclear Engineering GTATE OF TEXAS )
)
)
Subscribedapdsworntobeforeme,aNotaryPublicinandfor-
-The State of Texas thiad day of 2/cemkW/ , 1990.
O .
,digey,,,, "' : Notary Puutio in and for tue
" . gs,,,,/
< -Mewnentanian.,f State f Texas ,
1
="W I
1 A1/039.N19 i
, - - z $
- - Attachment 1 i
ST HL AE 3659 Page 1 of 4 RP.SPONSE TO GENERIC Lb"PTER 90-06 Generic Letter 90 06 provided resolution of Generic Issue 70,
- POWER OPERATED RELIEP VALVE AND BLOCK VALVE RELIABILITY," and Generic Issue 94, " ADDITIONAL LOW TEMPERATURE OVERPRESSURE PROTECTION POR LIGHT WATER REACTOR $". This Generic Letter requested that Licensees complete the actions identified in Section 3 of Enclosures A and B to enhance safety. Implementation of the requested actions resolves Generic Issues 70 and 94 for STPEGS. !
, 1 Section 3 of Enclosure A to Generic Letter 90 06 provides actions which should be taken to improve tLe reliability of Power Operated Relief Valves (PORVs) and block valves. Tho specific actions and the HL&P response are provided below:
Action 1.
Include PORVs and blotk valves within the scope of an operational quality )
assurance program that is in compliance with 10 CIR 50. Appendix B. This program should include the following elements:
- a. The addition of PORV.1 and block valves to the plant operational Quality Assurance Lint.
Response
The PORVs and block valves.are specified as safety class 1 valves and are included in the STPEGS Project Q List,
- b. ' Implementation of a maintenance / refurbishment program for PORVs and block valves that is based on the manufacturer's recommendations or guidelines and is implemented by trained plant maintenance personnel.
Response: ,
These valvea are included in the STPEGi meiutenance program which incorporates the manufactuier's guidelines and reconnendations. Required maintenance is specified in thu Grecial Equipment Qualification Maintenance Book (SEQHB) and is performed by trained maintenance personnel.
- c. When repinecoent parts and spares, as well as complete components, are required for existing non safoty grado PORVs and block valves (and associated control systems), it is the intent of this generic letter that these items may be procured in accordance with the original construction codes and standards.
Response
The STPEGS PORVs and block valves are safety grade valves. Repincement parts, spares and components are procured in accordance with the original construction codes and standards.
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Attachment 1 l ST ill AE 36$9 j
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! Action 2. ;
Include PORVs, valves in PORV control air systems, and block valves i within the scope of a program covered by subrection IWV,
- Inservice Testing of Valves in Nuclear Power Plants," of Section XI of the ASME 4 2
Boiler and Pressure Vessel code. Stroke testing of PORVs should only bc ,
performed during Mode 3 (HOT STANDBY) or Mode 4 (110T SHUTDOWN) and in all j cases prior to establishing conditions where the PORVs are used for l low temperature overpressure protection. Stroke testing of the PORVs l should not be performed during power operation. Additionally, the PORV l block valves should be included in the licensees' expanded MOV test 4
program discussed in NRC Generic Letter 89 10, " Safety Related Motor Operated Valve Testing and Surveillance," dated June 28, 1989.
Response
The STPECS solenoid operated PORVs and block valves are included in the ,
inservice Inspection (ISI) program which is covered by Subsection IWV of j Section XI of the ASME code. Stroke testing of the PORVs will not be !
[ performed during power operations. The conditions under which PORV j stroke testing is performed are provided in Technleni Specification '
Requirements 4.4.4.1.b 3.4.9.3.b, and 3.4.9.3.c (see Reference 1). The PORV block valves are included-in the STPECS expanded MOV test program.
Action 3. '
For operating PWR plants, modify the limiting conditionts for operation of PORVs and block valves in the technical specifications for Modes 1. 2, and 3 to incorporate the position adopted by the str.ff in recent Ilcensing actions. Attachments A 1 through A 3 are provided for guidance. The staff recognizes that some recently licensed PWR plants already have technical specifications in accordance with the staff po-sition. Such plants are already in compliance with this position and need merely state that in their response. These recent technical speci*ications require that plants that run with the block valves closed (e.g., due to leaking PORVs) maintain electrical power to the block valves so they can be readily opened from the control room upon demand.
Additionally, plant operation in Modes 1, 2, and 3 with PORVs and block valves inoperable for reasons other than seat leakage is not permitted for periods of more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Response
The guidance provided in Attachment A-1 through A 3 of the Generic Letter is incorporated in-the proposed revision to the STPECS Technical Specifications. The proposed Technical Specification changes which incorporate this guidance are given in Reference.1.
Section 3 of Enclosure B to Generic Letter 90 06 provides additional administrative restrictions on the Low Temperature Overpressure Protection (LTOP) system which improve the protection system availability. As stated in the Staff position, revision of the current Technical Specification for i Overprotection Protection to reduce the A0T for a single channel in modes 5 1.
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Attachment 1 ST.}lL. AE. 3659 Page 3 of 4 and 6 from 7 days to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provides additional assurance that plant operation is consistent with the design basis transient analysis. In addition, the Staff has requested that administrative controls and procedures which are identified in Section 1 of Enclosure B to the Generic Letter and which are incorporated into the plant design basis should be implemented now 1R the teatrictions were not implemented as part of USI A 26. These administrative controls and procedures shich were identified as part of Multi-Plant Action Item B 04 include the following items:
- 1. Minimize the time the reactor coolant system (RCS) is maintained in a water solid condition.
- 2. Restrict the number of high pressure pumps operable to no more than one when the RCS is in the LTOP condition.
- 3. Ensure that-the steam generator to RCS temperature difference is less than 50 Deg F when a reactor coolant pump (RCP) is bein6 started in a water solid RCS.
4 Set the PORV setpoint (if the particular plant relies on this 1 component for LTOP) to a plant + specific analysis supported value, and have surveillance that checks the PORV actuation electronics and setpoint.
Response
The revised Technical Specification for the STPECS Cold Overpressure Mitigation System (COMS) is provided in Reference 1. This revised Technical Specification 3.4.9.3 reduces the A0T from 7 days to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as requested. The administrative controls and procedures discussed in Section 1 of Enclosure B of the Generic Letter are incorporated into the STPECS procedures as follows:
- 1. The time that the RCS is water solid is minimized by the STPECS plant operating procedures and administrative controls. The RCS is placed in a water solid condition only during cooldown and filling and venting operatiens. The need to minimize the time that the plant is maintained in a water solid condition will be included in operator training.
- 2. The current STPECS Technical Specifications allow only one liigh llead Safety Injection (511151) pump to be OPERABLE and a second lillS1 pump OPERABhE with its dreaker racked out in MODE 4 (ref. Technical specification LCO 3.u.3 1). All 111151 pumps are to be inoperabic in HODES 5 & 6 with the reactor vessel head on (ref. Technical Specification LCO 3.5.3.2). The current STPEGS Technical Specification requirements comply with the intent of item 2 of Multi-Plant Action item.
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At t achinent 1 i
ST l!L AE 3659 Page 4 of 4
- 3. The restriction on starting a RCP during water solid operations with the steam generator secondary side water temperature greater than 50*F above the RCS temperature is provided in the current STPECS Technical Specifications (ref. Technical Specification LCO 3.4.1.3).
- 4. The PORV setpoints are based on plant specific analysis which ensures compliance with the 10 CFR 50 Appendix G liroits. The surveillance requirements for the PORV actuation electronics and setpoints are provided in current Technical Specification Requirements 4.4.4.1.a.
4.4.9.3.1.a and 4.4.9.3.1.b.
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